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@ARTICLE{Franke:844549,
      author       = {Franke, T. and Agostinetti, P. and Avramidis, K. and Bader,
                      A. and Bachmann, Ch. and Biel, W. and Bolzonella, T. and
                      Ciattaglia, S. and Coleman, M. and Cismondi, F. and
                      Granucci, G. and Grossetti, G. and Jelonnek, J. and Jenkins,
                      I. and Kalsey, M. and Kembleton, R. and Mantel, N. and
                      Noterdaeme, J.-M. and Rispoli, N. and Simonin, A. and
                      Sonato, P. and Tran, M. Q. and Vincenzi, P. and Wenninger,
                      R.},
      title        = {{H}eating $\&$ current drive efficiencies, {TBR} and {RAMI}
                      considerations for {DEMO}},
      journal      = {Fusion engineering and design},
      volume       = {123},
      issn         = {0920-3796},
      address      = {New York, NY [u.a.]},
      publisher    = {Elsevier},
      reportid     = {FZJ-2018-01956},
      pages        = {495 - 499},
      year         = {2017},
      abstract     = {The heating $\&$ current drive $(H\&CD)$ systems in a
                      DEMOnstration fusion power plant are one of the major energy
                      consumers. Due to its high demand in electrical energy the
                      $H\&CD$ efficiency optimization is an important goal in the
                      DEMO development.The $H\&CD$ power for DEMO, based on
                      physics scenarios for the different plasma phases, is needed
                      for plasma initiation phases (incl. breakdown), current
                      ramp-up, heating to H-mode, burn control, controlled current
                      ramp-down, MHD control and other functions. Plasma control
                      will need significant installed $H\&CD$ power, though not
                      continuously used.Previously, in the DEMO1 2015 baseline
                      definitions, optimistic forecasted $H\&CD$ efficiencies had
                      been assumed in the corresponding system code (i.e. PROCESS)
                      module. Realizing that there is a high uncertainty in the
                      assumptions the efficiencies have been modified and the
                      impact on the DEMO power plant and basic tokamak
                      configuration are discussed in this article.A comparison of
                      the various $H\&CD$ systems NBI (Neutral Beam Injection),
                      Electron Cyclotron (EC), Ion Cyclotron (IC) in terms of
                      impact on Tritium Breeding Ratio (TBR) due to various
                      openings for the $H\&CD$ front end components in the
                      breeding blanket (BB) is presented.For increasing the
                      reliability as major features the power per system unit and
                      the redundancy are identified leading to a new proposal for
                      clusters for EC and modular ion-sources for NB.},
      cin          = {IEK-4},
      ddc          = {620},
      cid          = {I:(DE-Juel1)IEK-4-20101013},
      pnm          = {174 - Plasma-Wall-Interaction (POF3-174)},
      pid          = {G:(DE-HGF)POF3-174},
      typ          = {PUB:(DE-HGF)16},
      UT           = {WOS:000418992000101},
      doi          = {10.1016/j.fusengdes.2017.02.007},
      url          = {https://juser.fz-juelich.de/record/844549},
}